Class / Patent application number | Description | Number of patent applications / Date published |
376308000 | FISSION REACTOR MATERIAL (INCLUDING REACTION PRODUCTS) TREATMENT | 55 |
20090252275 | Chemical Enhancement of Ultrasonic Fuel Cleaning - A method for cleaning an irradiated nuclear fuel assembly includes chemically enhancing a technique utilizing an apparatus including a housing adapted to engage a nuclear fuel assembly. A set of ultrasonic transducers is positioned on the housing to supply radially emanating omnidirectional ultrasonic energy to remove deposits from the nuclear fuel assembly. Any corrosion products remaining after ultrasonic fuel cleaning will have exposed surfaces that are susceptible to chemical dissolution. | 10-08-2009 |
20090323885 | Devices, Systems, and Methods Comprising Graphite Having an Enhanced Neutron Diffusion Coefficient for Enhancing Power Reactor Performance - The present invention relates to the field of energy generation. More particularly, the present invention relates to devices, systems, and methods for use in generating energy with graphite-moderated nuclear reactors. Embodiments of the invention include devices, systems, and methods for use in generating power that use graphite having a neutron diffusion coefficient higher than that of Acheson graphite. Specifically included embodiments comprise providing artificial graphite manufactured under high pressure during the graphitization process to cause a larger neutron diffusion coefficient than graphite not produced under pressure (Acheson graphite). Suitable graphite according to the invention includes graphite prepared under high pressure during the graphitization phase of the manufacturing process, which produces graphite with an increased diffusion coefficient by reducing the microcrystal diffraction scattering and increasing the non-diffractive (inelastic) scattering of the graphite. | 12-31-2009 |
376309000 | Post accident impurity or contaminant removal | 5 |
20130170600 | POST-ACCIDENT FISSION PRODUCT REMOVAL SYSTEM AND METHOD OF REMOVING POST-ACCIDENT FISSION PRODUCT - A post-accident fission product removal system may include an air mover, a filter assembly, and/or an ionization chamber. The air mover may be configured to move contaminated air through the filter assembly to produce filtered air. The ionization chamber may be connected to the filter assembly. The ionization chamber may include an anode and a cathode. The ionization chamber may be configured to receive the filtered air from the filter assembly and to ionize and capture radioisotopes from the filtered air to produce clean air. | 07-04-2013 |
20130208847 | ENHANCED NUCLEAR SUMP STRAINER SYSTEM - In accordance with the present invention, there is provided a strainer system for use in a nuclear sump. The strainer system of the present invention includes at least one primary strainer module which defines a primary strainer/filter surface. In the strainer system, the primary strainer surface of the primary strainer module has a debris interceptor which is cooperatively engaged thereto, and may be outfitted with one or more pressure released or activated membranes. In a loss of coolant accident, the debris interceptor, alone or in combination with the pressure activated membrane(s), is adapted to reduce the differential pressure experienced across the strainer system in nuclear power plants with medium to high fiber loads. | 08-15-2013 |
20140161218 | RADIOACTIVE CAPTURE SYSTEM FOR SEVERE ACCIDENT CONTAINMENT OF LIGHT WATER REACTORS (LWRS), AND METHOD THEREOF - A system and a method for capturing gaseous, particulate and liquid radioactive material released from primary containment of a Light Water Reactor (LWR) during severe accident conditions. The system includes a below-grade media area, connected to a reactor pressure vessel (RPV) and portions of primary containment, providing varying levels of adsorption/absorption of the radioactive material. The media area is located on-site to offer a passive, self-regulating structure for stabilizing a nuclear reactor. The capture system provides for liquid drainage and gaseous venting of the radioactive material, and a treatment capable of treating the media following stabilization of the reactor. | 06-12-2014 |
20140270046 | SYSTEM FOR ABATEMENT OF NOXIOUS EMISSIONS IN THE ATMOSPHERE FROM AN INDUSTRIAL OR NUCLEAR POWER PLANT - A system for the abatement of noxious emissions from an industrial or nuclear power plant or the like in the event of accident includes a structure for impermeabilization of the ground, which extends at least in an annular area that surrounds the plant, a plurality of water-sprinkling towers, which are arranged around the plant and sprinkle water in the atmosphere, preferably added with chemical and/or biological and/or mineral substances, and a peripheral collection structure, configured for receiving water withheld by the impermeabilization structure. | 09-18-2014 |
20150357063 | NUCLEAR POWER PLANT AND REACTOR BUILDING GAS TREATMENT SYSTEM - A nuclear power plant according to an embodiment comprises: a reactor well; a reactor well upper lid; an operation floor; an operation floor area wall; a standby gas treatment system; and a reactor well exhaust section to release the gas inside the reactor well to the environment without releasing the gas into the operation floor area in an event of a severe accident. The standby gas treatment system includes: a suction pipe to take in gas inside the reactor building; an exhaust fan; a standby gas treatment system exhaust pipe; a heater that is disposed between the suction pipe and the standby gas treatment system exhaust pipe; and a filter to filter the gas heated by the heater and to send the gas to the standby gas treatment system exhaust pipe. | 12-10-2015 |
376310000 | Impurity removal | 48 |
20090003509 | Suppression Method of Radionuclide Deposition on Reactor Component of Nuclear Power Plant and Ferrite Film Formation Apparatus - A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film. | 01-01-2009 |
20100195783 | Automated Cleaning Equipment and Method for the Nuclear Fuel-Cladding Tube - Disclosed is an apparatus for performing an automated cleaning of nuclear fuel cladding-tubes. The apparatus comprises a pre-cleaning holding section disposed at a first side of the apparatus, a primary cleaning-material supplying section and a primary cleaning section disposed at a second side of the apparatus, a secondary cleaning section and a secondary cleaning material supplying section disposed at the second side of the apparatus and beside the primary cleaning section, an inspection section disposed at a third side of the apparatus that is opposite to the second side, and a post-cleaning holding section disposed at the fourth side of the transferring section. The pre-cleaning holding section and the post-cleaning holding section includes a cladding-tube guide where the cladding-tube is loaded before and after cleaning. Primary and secondary cleaning material supply sections are disposed at a lateral side of the primary and secondary cleaning sections respectively. | 08-05-2010 |
20110116590 | Device And Method For The Automated Decontamination Of A Nuclear Fuel Rod - A method for the surface tribological decontamination of nuclear fuel rods automates surface wiping by one or more bands of fabric. The band is distant from the axis of the rod, the rod is placed facing the band, and then the band is tensioned around the surface of the rod and moved. The rod may be immobile, moved in pure translation along its axis or with a wide-step helical movement. Preferably, the decontamination is carried by two bands simultaneously, so as to cover the total surface in one pass of the rod. | 05-19-2011 |
20110122986 | METHOD OF INHIBITING ADHESION OF RADIOACTIVE SUBSTANCE AND APPARATUS INHIBITED FROM SUFFERING ADHESION THEREOF - The present invention relates to a method and an apparatus for suppressing adhesion of a radioactive substance, capable of suppressing adhesion of the radioactive substance onto the surface of a metallic material forming a structural member in a nuclear plant. On the surface of the metallic material forming the structural member in a nuclear power generation plant, e.g., a surface | 05-26-2011 |
20120183115 | LIGHT WATER REACTOR PRIMARY COOLANT ACTIVITY CLEANUP - A method for the cleanup of ionic species such as cobalt and nickel in nuclear power plant aqueous streams using a sequestration resin material is disclosed herein. The method includes the steps of providing a sequestration resin for removal of radioisotopes of transition metal impurities contained in the plant process streams, and distributing the sequestration resin into the plant process streams such that the sequestration resin interacts with the process streams and removes the transition metal impurities. | 07-19-2012 |
20140205052 | Chelate Free Chemical Decontamination Reagent for Removal of the Dense Radioactive Oxide Layer on the Metal Surface and Chemical Decontamination Method Using the Same - A chemical decontamination reagent containing a reducing agent, a reductive metal ion, and an inorganic acid is provided to remove a radioactive oxide layer on a metal surface. The reagent can dissolve the radioactive oxide layer on the metal surface effectively at a relatively low temperature and enables a simple process of contacting the reagent to the radioactive oxide, thus economically effective in terms of cost and time required for the process. Since the decontamination does not use a conventional organic chelating agent such as oxalic acid, but the reducing agent as a main substance, the residuals of the reducing agent remained after decontamination can be decomposed and removed with an oxidizing agent. Due to the easy decomposition with the chemical decontamination reagent, secondary wastes can be minimized and the radionuclides remained in the decontamination reagent solution can be removed effectively. | 07-24-2014 |
20150146839 | DEVICES AND METHODS FOR MANAGING NONCOMBUSTIBLE GASSES IN NUCLEAR POWER PLANTS - Systems passively eliminate noncondensable gasses from facilities susceptible to damage from combustion of built-up noncondensable gasses, such as H2 and O2 in nuclear power plants, without the need for external power and/or moving parts. Systems include catalyst plates installed in a lower header of the Passive Containment Cooling System (PCCS) condenser, a catalyst packing member, and/or a catalyst coating on an interior surface of a condensation tube of the PCCS condenser or an annular outlet of the PCCS condenser. Structures may have surfaces or hydrophobic elements that inhibit water formation and promote contact with the noncondensable gas. Noncondensable gasses in a nuclear power plant are eliminated by installing and using the systems individually or in combination. An operating pressure of the PCCS condenser may be increased to facilitate recombination of noncondensable gasses therein. | 05-28-2015 |
20150364226 | METHOD FOR THE SURFACE DECONTAMINATION OF COMPONENT PARTS OF THE COOLANT CYCLE OF A NUCLEAR REACTOR - The invention relates to a process for the chemical decontamination of a surface, having an oxide layer of a metallic component of the coolant system of a nuclear power station, which comprises at least one oxidation step in which the oxide layer is treated with an aqueous solution containing an oxidant and a subsequent decontamination step in which the oxide layer is treated with an aqueous solution of a decont. acid which has the property of forming a sparingly soluble precipitate with metal ions, in particular with nickel ions. Prior to carrying out the decontamination step, metal ions which have gone into solution during the oxidation step are removed from the aqueous solution by means of a cation exchanger. | 12-17-2015 |
20160019993 | Apparatus and Method for Stripping Tritium from Molten Salt - A method of stripping tritium from flowing stream of molten salt includes providing a tritium-separating membrane structure having a porous support, a nanoporous structural metal-ion diffusion barrier layer, and a gas-tight, nonporous palladium-bearing separative layer, directing the flowing stream of molten salt into contact with the palladium-bearing layer so that tritium contained within the molten salt is transported through the tritium-separating membrane structure, and contacting a sweep gas with the porous support for collecting the tritium. | 01-21-2016 |
20160111175 | MECHANICAL COMPONENT - This disclosure concerns reducing or elimination the build-up of coolant materials in the fuel handling and component maintenance systems of nuclear reactors, thereby reducing or eliminating manual cleaning of said components. A mechanical component ( | 04-21-2016 |
376311000 | Reprocessing of fuel during reactor operation | 2 |
20160189813 | MOLTEN NUCLEAR FUEL SALTS AND RELATED SYSTEMS AND METHODS - This disclosure describes nuclear fuel salts usable in certain molten salt reactor designs and related systems and methods. Binary, ternary and quaternary chloride fuel salts of uranium, as well as other fissionable elements, are described. In addition, fuel salts of UCl | 06-30-2016 |
20220139577 | ANTI-PROLIFERATION SAFEGUARDS FOR NUCLEAR FUEL SALTS - An anti-proliferation technique is disclosed to reduce the likelihood of nuclear proliferation due to the use fissionable fuel salts. The technique includes doping the fuel salt with one or more elements (referred to herein as activation dopants) that, upon exposure to neutrons such as would occur in the fuel salt when a reactor is in operation, undergo a nuclear reaction to, directly or indirectly, form highly active “protecting isotopes” (of the same element as the activation dopant or a different element). A sufficient mass of activation dopants is used so that the Figure of Merit (FOM) of the fuel salt is decreased to below 1.0 within some target number of days of fission. This allows the FOM of the fuel salt to be controlled so that the fuel becomes too dangerous to handle before to the creation of a significant amount of weaponizable isotopes. | 05-05-2022 |
376313000 | By filters, ion exchangers, or absorbers | 32 |
20090060114 | DEBRIS SHIELD FOR UPPER TIE PLATE IN A NUCLEAR FUEL BUNDLE AND METHOD FOR FILTERING DEBRIS - A nuclear reactor fuel assembly including: an upper tie plate having apertures to receive and support fuel rods of a fuel bundle; the fuel bundle includes an array of the fuel rods mounted and housed in the walls of a channel, and a load bearing or non-load bearing debris shield may be mounted in the upper tie plate, wherein the debris shield is porous to prevent the passage of debris. The debris shield is mounted in the frame of the upper tie plate. The debris shield can be either a removable unit, or it can be attached as a permanent integrated structure within the upper tie plate. The upper tie plate frame is also porous, e.g., has small vertical openings to allow fluid to pass through the frame and block passage of debris. The openings in the frame increase the effective flow area of passages through the upper tie plate and thereby compensate or offset any flow restrictions due to the debris shield. Preventing debris falling into the fuel bundle is expected to assure the operational life of the fuel assembly by reducing the risk of fuel rod failure and premature discharge from the reactor core. | 03-05-2009 |
20090080590 | METHOD AND APPARATUS TO SHIELD A NUCLEAR FUEL ASSEMBLY WITH REMOVABLE DEBRIS SHIELD IN UPPER TIE - A method to capture, retain and remove debris falling into a nuclear reactor fuel bundle assembly including a bundle of fuel rods mounted below an upper tie plate and housed in a hollow metal channel, the method includes: inserting a debris shield in the upper tie plate; maintaining the shield in the upper tie plate and above the fuel rods, and water rods, while the fuel bundle assembly is in an operating nuclear reactor core; capturing debris falling in the fuel assembly on the debris shield; after capturing the debris, removing the fuel bundle assembly with the inserted debris shield from the nuclear reactor core to a maintenance/fuel inspection pool and thereafter removing the debris shield from the upper tie plate, cleaning and then reinserting the cleaned debris shield back into the upper tie plate, and moving the fuel bundle assembly from the maintenance/fuel inspection pool back into the nuclear reactor core. | 03-26-2009 |
20090092217 | METHOD TO SHIELD NUCLEAR FUEL ASSEMBLY WITH REMOVABLE DEBRIS SHIELD IN UPPER TIE PLATE - A method to prevent debris falling into a nuclear reactor fuel assembly including a bundle of fuel rods mounted below an upper tie plate and housed in a channel including: inserting a debris shield in the upper tie plate; maintaining the shield in the upper tie plate and above the fuel rods, while the fuel assembly is in an operating nuclear reactor core; flowing coolant through the bundle and the debris shield during operation of the nuclear reactor core, and capturing or deflecting debris falling in the fuel assembly with the debris shield. | 04-09-2009 |
20090185653 | Suppression Method of Radionuclide Deposition on Reactor Component of Nuclear Power Plant and Ferrite Film Formation Apparatus - A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film. | 07-23-2009 |
20090296873 | METHOD AND APPARATUS FOR CONDENSATE DEMINERALIZATION - A method and an apparatus for performing a condensate demineralization treatment within a condensate demineralization apparatus of a nuclear power plant, which are capable of producing a high-purity treated water containing a low concentration of sulfate ions derived from the TOC eluted from a cation exchange resin. A condensate demineralization method for performing a demineralization treatment of a condensate from a nuclear power plant using an ion exchange resin, wherein the demineralization treatment of the condensate is performed by bringing the condensate into contact with an ion exchange resin bed that includes a mixed bed prepared by uniformly mixing a strongly acidic gel-type cation exchange resin and a strongly basic type 1 porous anion exchange resin having a cross-linking within a range from 1% to 4%. | 12-03-2009 |
20090310733 | DEMINERALIZER OF PRIMARY COOLANT SYSTEM IN PRESSURIZED-WATER REACTOR POWER PLANT AND METHOD FOR PURIFYING PRIMARY COOLING WATER IN PRESSURIZED-WATER REACTOR POWER PLANT - By using a boric acid-resistant anion exchange resin as the anion exchange resin used in a demineralizer that purifies the primary cooling water in a pressurized-water reactor power plant, even when a boric acid-containing primary cooling water is brought into contact with the anion exchange resin disposed in the demineralizer, the generation of breaking or cracking in the anion exchange resin can be prevented. | 12-17-2009 |
20100135451 | Debris Trap - A debris trap catches debris falling through a fuel bundle orifice in a nuclear reactor. The debris trap includes a shaft and a debris capture tray attached to an end of the shaft. The debris capture tray includes a tray cavity sized larger than the fuel bundle orifice. | 06-03-2010 |
20110051879 | DEBRIS MITIGATION UPPER TIE PLATES AND FUEL BUNDLES USING THE SAME - Example embodiments are directed to upper tie plates for debris mitigation and fuel bundles that use the upper tie plates. Example embodiment tie plates may include a plurality of debris capture features that overlap each other so as to create debris traps for particulate debris that would fall onto the fuel bundle. Example embodiment fuel bundles may use the upper tie plates for debris mitigation. | 03-03-2011 |
20110103538 | RADIOACTIVE DEBRIS TRAP - A radioactive debris trap to be installed in a steam generator for removing debris in the primary flow of a nuclear power plant's primary heat transport system. The debris trap includes an outer cylinder and a coaxial inner cylinder both having a top end and a bottom end. A top plate connects the top ends of the outer and inner cylinders. A bottom plate which encloses the trap is connected to the bottom end of the outer cylinder. There is a gap between the bottom end of the inner cylinder and the bottom plate through which primary flow enters a settling chamber located in an annular gap between the outer and inner cylinders. Several small holes are located at the top end of the outer cylinder through which liquid exits the debris trap. A means for fixedly connecting the debris trap to the steam generator is provided on the outer surface of the outer cylinder. Also included is a means for removing the radioactive debris trap from the steam generator without exposing personnel to excessive radiation. | 05-05-2011 |
20110158373 | Nuclear Fuel Assembly Bottom Nozzle - A nuclear fuel assembly bottom nozzle, of the type including a perforated plate to allow water to pass through it, the nozzle having lateral faces, and at least one anti-debris element positioned on a lateral face to block out debris likely to infiltrate between the bottom nozzle and another adjacent bottom nozzle, characterized in that, in the free state, the or each anti-debris element permanently projects from the lateral face on which it is positioned, the or each anti-debris element being elastically deformable so as to retract towards the lateral face in the event of a force being exerted on the anti-debris element towards the lateral face. | 06-30-2011 |
20110164719 | NUCLEAR FUEL ASSEMBLY DEBRIS FILTER BOTTOM NOZZLE - A debris filter bottom nozzle for a pressurized water nuclear reactor fuel assembly that employs a corrugated screen in combination with flow through holes in an adapter plate to filter out potentially damaging debris. The area between the screen and the adapter plate defines a plenum that forms a collection point for the debris and coolant access is provided to the plenum through openings in the screen and sidewalls of the nozzle. | 07-07-2011 |
20110170651 | FILTER FOR SEPARATING PARTICLES IN A COOLANT FLUID IN A NUCLEAR REACTOR - A filter is provided which includes channels for circulation of coolant fluid through the filter, at least one channel extending along a channel centerline and includes an upstream section, a downstream section and an intermediate section extending between the upstream section and the downstream section and being enlarged relative to the upstream section and the downstream section. | 07-14-2011 |
20110268240 | DEBRIS FILTER FOR USE IN A NUCLEAR FUEL ASSEMBLY - A filter including a plurality of flow ducts extending in a longitudinal direction and each delimited between one pair of walls. | 11-03-2011 |
20110286568 | Boiling Water Nuclear Plant and Method of Reducing Dose in Turbine System - An adsorbing substance made of a material having an acid center in its molecular frame is installed in a passage for steam generated in a reactor pressure vessel | 11-24-2011 |
20110317798 | Debris Trap - A debris trap catches debris falling through a fuel bundle orifice in a nuclear reactor. The debris trap includes a shaft and a debris capture tray attached to an end of the shaft. The debris capture tray includes a tray cavity sized larger than the fuel bundle orifice. | 12-29-2011 |
20120207262 | Debris Exclusion and Retention Device for a Fuel Assembly - A debris exclusion and retention device traps and retains foreign material within the lower tie plate of the fuel assembly utilizing the existing flow paths within the lower tie plate, and without redirecting coolant flow. Flow through the inlet nozzle of the lower tie plate into an enlarged lower tie plate housing creates strong jet impingement against the center of the lower tie plate grid or debris filter, if present, which has a tendency to push debris to the periphery of the lower tie plate. Low flow zones around the periphery of the lower tie plate allow debris to fall back toward the inlet nozzle. The retention device traps and retains debris in these low flow zones without impacting existing flow patterns in the lower tie plate. Thus, the retention device has minimal or no impact on lower tie plate pressure drop. | 08-16-2012 |
20120243652 | BWR NUCLEAR FUEL ASSEMBLY WITH NON-RETAINED PARTIAL LENGTH FUEL RODS - A nuclear fuel assembly for a boiling water reactor is provided. The nuclear fuel assembly includes a base, a head and a bundle of full length fuel rods and partial length fuel rods. The bundle extends longitudinally between the base and the head, at least one partial length fuel rod having a lower end received in a housing provided in the base and delimited by a closed bottom larger than the lower end. The housing is further delimited by a peripheral wall surrounding the lower end and the partial length fuel rod rests freely on the bottom. | 09-27-2012 |
20120307957 | FUEL HANDLING AREA PASSIVE FILTRATION DESIGN - The present invention relates to a passive filtration system for a fuel handling area having a spent fuel pool in a nuclear reactor. The passive filtration system reduces a discharge into the atmosphere of particulates, such as radioactive particulates, generated in a spent fuel pool boiling event. The passive filtration system includes a discharge path, a vent mechanism positioned between the fuel handling area and the discharge path. The vent mechanism is structured to release a steam and air mixture from the fuel handling area to the discharge path. The steam and air mixture includes the particulates. The passive filtration system further includes an air filtration unit located in the discharge path and this unit has at least one passive filter. The steam and air mixture is forced through the at least one passive filter due to a differential pressure generated in the fuel handling area. The at least one passive filter traps particulates from the steam and air mixture to produce a filtered steam and air mixture that is released through a second vent mechanism into the atmosphere. | 12-06-2012 |
20130003909 | FILTER FOR COOLING WATER OF A PRIMARY CIRCUIT OF A NUCLEAR POWER STATION, AND A METHOD FOR FILTERING COOLING WATER - A filter is provided for cooling water conducting primary circuit of a nuclear power station. The power station contains a reactor container with a discharge opening for the cooling water that opens into the interior of the reactor container and being accessed when the power station is brought to a stop for an inspection shutdown. The filter contains a base carrier with an entrance, at least one filter cartridge held on the base carrier and is fluidically coupled to the entrance, and a fixing device that can be fixed to the discharge end such that the entrance couples fluidically to the discharge opening. In a method for filtering cooling water during the inspection shutdown a filter is fixed, by its fixing device, with its entrance in fluid connection with the discharge opening, the cooling water is circulated through the discharge opening, and the filter is removed from the discharge opening. | 01-03-2013 |
20130170601 | PARTICULATE REMOVAL SYSTEM - A particulate removal apparatus and method are used to capture and remove particulates from nuclear reactor core coolant during normal operation. Bottom nozzle, particulate removal apparatus and top nozzle structures form an assembly sized to be installed in place of a nuclear fuel assembly. The particulate removal achieved reduces the inventory of corrosion product deposits, foreign objects and other particulates in the reactor coolant system. This in turn reduces activation or deposition of particulates on fuel cladding, with a corresponding improvement in fuel reliability and reduction in ex-core radiation fields. | 07-04-2013 |
20130259185 | RADIOACTIVE DEBRIS TRAP - A radioactive debris trap to be installed in a steam generator for removing debris in the primary flow of a nuclear power plant's primary heat transport system. The debris trap includes an outer cylinder and a coaxial inner cylinder both having a top end and a bottom end. A top plate connects the top ends of the outer and inner cylinders. A bottom plate which encloses the trap is connected to the bottom end of the outer cylinder. There is a gap between the bottom end of the inner cylinder and the bottom plate through which primary flow enters a settling chamber located in an annular gap between the outer and inner cylinders. Several small holes are located at the top end of the outer cylinder through which liquid exits the debris trap. A means for fixedly connecting the debris trap to the steam generator is provided on the outer surface of the outer cylinder. Also included is a means for removing the radioactive debris trap from the steam generator without exposing personnel to excessive radiation. | 10-03-2013 |
20130272477 | Pressurized Water Reactor with Skirted Lower End Fitting and Filter Plate - In a nuclear reactor core having fuel assemblies with upper and lower end fittings, a debris filter plate is attached to a lower end fitting having a skirt. The filter prevents debris from entering the fuel assembly, while the skirt prevents the trapped debris from sliding off the lower end fitting and continuing into the core. The lower end fitting is formed from a substantially square base and has flow channels to allow coolant to flow through it to the fuel assembly. The skirt is an extension of the metal of the lower end fitting that extends around the perimeter of the lower end fitting, spanning all four corners of the lower end fitting. In addition to capturing debris, the skirt also positions the filter, which may be manufactured from the same metal as the lower end fitting. | 10-17-2013 |
20140056397 | DEBRIS FILTER FOR NUCLEAR REACTOR INSTALLATION AND NUCLEAR FUEL ASSEMBLY COMPRISING SUCH A DEBRIS FILTER - A debris filter for a nuclear reactor installation is provided. The debris filter comprises a plurality of plates arranged side-by-side in a spaced relationship and delimiting between them flow passages extending through the debris filter from a lower inlet face to an upper outlet face of the debris filter, each passage having an intermediate section offset with respect to an inlet section and an outlet section. At least one of the plates is formed with debris catching features distributed along the plate and protruding into at least one passage delimited by the plate. | 02-27-2014 |
20140064428 | LOWER NOZZLE FOR USE IN NUCLEAR FUEL ASSEMBLY - A lower nozzle for use in a nuclear fuel assembly provided. The lower nozzle is of the type having an axis and comprising a transverse lower tie plate for channelling the coolant through the lower tie plate and a tubular skirt extending axially from the periphery of the lower tie plate, the skirt delimiting an axial housing closed at one end by the lower tie plate and open at the opposite end, a debris filter configured for axial insertion in the housing and snap-fit springs for retaining the debris filter in the housing after insertion. The springs are configured to shift the debris filter axially towards the lower tie plate. | 03-06-2014 |
20140064429 | MULTIMODAL DEBRIS TRAP - In a debris trap that may be used in an Emergency Core Cooling System of a nuclear power plant, the filter media is arranged to define both filtration and bypass flowpaths that are in fluid communication with one another. At least initially, each of the filtration and bypass flowpaths are open, and the filtration and bypass flowpaths have relatively low and relatively high head loss, respectively. The debris trap is operative so that flow through the debris trap may passively, and typically gradually, transition from the filtration flowpaths to the bypass flowpath in response to the filter media collecting increasing amounts of debris. More specifically, initially substantially all of the flow may be through the filtration flowpaths, and thereafter the filtration flowpaths may become substantially obstructed so that substantially all of the flow is through the bypass flowpath. | 03-06-2014 |
20150049852 | SYSTEMS, METHODS, AND FILTERS FOR RADIOACTIVE MATERIAL CAPTURE - A system configured to passively filter radioactive materials from a flow may include one or more particulate removal devices; one or more water removal devices; and/or one or more radionuclide removal devices. At least one of the one or more particulate removal devices may mechanically remove particulates of the radioactive materials from the flow. At least one of the one or more water removal devices mechanically may remove water from the flow. At least one of the one or more radionuclide removal devices may remove radioactive aerosols, reactive radioactive gases, or radioactive aerosols and reactive radioactive gases from the flow using engineered filter media. A filter may include a body, including an inlet and an outlet. The body may be configured to store filter media, to contain pressure from gas explosions, and/or to allow the stored filter media to move toward the outlet when pressure at the inlet increases. | 02-19-2015 |
20150117588 | PURIFICATION METHOD AND APPARATUS FOR SPENT FUEL POOL WATER AFTER NUCLEAR POWER GENERATION AND TREATMENT METHOD AND APPARATUS FOR SPENT FUEL POOL WATER - A purification method for spent fuel pool water from nuclear power generation, the method comprising: passing the water at a linear flow velocity of 50 m/h or less through a purification apparatus for the water comprising an ion exchange resin layer and a metal-doped resin layer which is laid at a bed height of 2 cm or more on a surface layer of the ion exchange resin layer wherein the water to be treated is contacted with the metal-doped resin layer to decompose a pro-oxidant contained in the water; and subsequently contacting the water with the ion exchange resin. | 04-30-2015 |
376314000 | Gas filters (e.g., adsorbers) | 3 |
20110216872 | Boiling Water Nuclear Plant and Steam Dryer - In the boiling water nuclear plant of the present invention, a steam dryer is disposed in a reactor pressure vessel. Materials that have capability of capturing nitrogen compounds containing N-16 are supported on porous member. The porous members are placed in a region where steam goes through in the steam dryer. For example, both or either of perforated plates installed in the steam dryer is constituted of the porous member on which N-16 capture material is supported. When steam containing N-16 goes through the perforated plates, the N-16 is captured by the porous member, whereby the N-16 transfer amount into the turbine system is reduced. | 09-08-2011 |
20130279641 | METHOD TO EXTRACT TRITIUM FROM IRRADIATED BOILING WATER REACTOR CONTROL ROD BLADES - A method for extracting tritium from irradiated boiling water reactor control rods that have cruciform-shaped. Bands of a malleable metal are wrapped around the flat portions of the blades, one band near the top of each blade panel and a second band near the bottom. The bands are crimped and an inlet penetration is formed through one of the bands and the panel and an outlet penetration is formed through the second band and the panel. A termination of each end of a closed loop conduit is sealably connected to the inlet and outlet for transporting a carrier gas through the interior of the panel. The carrier gas passing through the interior transports the tritium out of the panel to a tritium getter filter to capture the tritium. The carrier gas then recirculates through the system. | 10-24-2013 |
20140010340 | FILTER FOR A NUCLEAR REACTOR CONTAINMENT VENTILATION SYSTEM - A wet filter for a nuclear reactor primary containment vent that employs an inclined manifold having a plurality of outlets that communicate through a first set of metal fiber filters submerged in a pool of water enclosed within a pressure vessel. A demister suspended above the pool of water to remove any entrained moisture in the filtered effluent before being passed through a second stage of higher density, dry, metal fiber filters connected to a second manifold that communicates with an outlet on the pressure vessel that is connected to an exhaust passage to the atmosphere. | 01-09-2014 |
376315000 | Electrostatic or magnetic filters | 2 |
20100260310 | Nuclear plant - This invention relates to a nuclear plant having a reactor vessel and a fluid circuit including flow path defining means, defining a flow path for circulating a reactor coolant fluid from and to the reactor vessel. The nuclear plant includes a particle collection zone defined along at least part of the length of the flow path, and particle deflection means arranged in particle deflecting relationship with the flow path to deflect particles from a fluid stream in the flow path into or toward the particle collection zone. | 10-14-2010 |
20120027157 | Nuclear Plant - This invention relates to a nuclear plant having a reactor vessel and a fluid circuit including flow path defining means, defining a flow path for circulating a reactor coolant fluid from and to the reactor vessel. The nuclear plant includes a particle collection zone defined along at least part of the length of the flow path, and particle deflection means arranged in particle deflecting relationship with the flow path to deflect particles from a fluid stream in the flow path into or toward the particle collection zone. | 02-02-2012 |
376316000 | By pressurized fluid (i.e., blowdown) | 4 |
20090010378 | STEAM GENERATOR DUAL HEAD SLUDGE LANCE AND PROCESS LANCING SYSTEM - A method of cleaning sludge from the tube sheet ( | 01-08-2009 |
20120269313 | STEAM GENERATOR DUAL HEAD SLUDGE LANCE - A moveable sludge lance ( | 10-25-2012 |
20140161219 | STEAM GENERATOR DUAL HEAD SLUDGE LANCE - A moveable sludge lance ( | 06-12-2014 |
20140233689 | Water Jet Peening Apparatus and Water Jet Peening Method - In a water jet peening apparatus, a high-pressure under-water pump is installed on an upper end of a casing and an injection nozzle drive mechanism equipped with an injection nozzle is attached to the casing. A high-pressure hose whose one end is connected to the high-pressure under-water pump is disposed in the casing and the other end of the high-pressure hose is connected to the injection nozzle. The casing is seated at an upper end of a control rod drive mechanism housing and the high-pressure under-water pump is driven. The high-pressure water pressurized by the high-pressure under-water pump is supplied to the injection nozzle through the high-pressure hose in the casing and is jetted toward the weld portion between the control rod drive mechanism housing and a stub tube. The time required for a water jet peening operation can be shortened. | 08-21-2014 |